05000254/LER-1997-030, Forwards LER 97-030-01 Re Instrument Line Excess Flow Valves Testing Performed at Less than Nominal Reactor Pressure Due to Inadequate Procedures.Ler Provides Addl Info Re Root Cause Analysis.Commitments Made by Util,Listed: Difference between revisions

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#REDIRECT [[05000254/LER-1997-030-01, Forwards LER 97-030-01 Re Instrument Line Excess Flow Valves Testing Performed at Less than Nominal Reactor Pressure Due to Inadequate Procedures.Ler Provides Addl Info Re Root Cause Analysis.Commitments Made by Util,Listed]]
| number = ML20217M539
| issue date = 03/27/1998
| title = Forwards LER 97-030-01 Re Instrument Line Excess Flow Valves Testing Performed at Less than Nominal Reactor Pressure Due to Inadequate Procedures.Ler Provides Addl Info Re Root Cause Analysis.Commitments Made by Util,Listed
| author name = Sager D
| author affiliation = COMMONWEALTH EDISON CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000254
| license number =
| contact person =
| document report number = SVP-98-116, NUDOCS 9804080127
| package number = ML20217M543
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
}}
{{LER
| Title = Forwards LER 97-030-01 Re Instrument Line Excess Flow Valves Testing Performed at Less than Nominal Reactor Pressure Due to Inadequate Procedures.Ler Provides Addl Info Re Root Cause Analysis.Commitments Made by Util,Listed
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000254
| LER year = 2097
| LER number = 30
| LER revision =
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
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SVP-98-116 March 27,1998 U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn:              Document Control Desk
 
==Reference:==
Quad Cities Nuclear Power Station Docket Number 50-254, DPR-29, Unit One Docket Number 50-265, DPR-30, Unit Two Enclosed is Licensee Event Report (LER) 97-030, Revision 1, for Quad Cities Nuclear Power Station. This event dealt with Instrument Line Excess Flow Valves Testing performed at less than nominal reactor pressure due to apparent inadequate procedures.
This report is being submitted to provide additional information following completion of the root cause analysis referenced in LER 97-030, Revision 0.
The following commitments are being made by this letter.
: 1. The instmment maintenance procedure (QCIS 0200-22) will be revised to perform just-in-time training on the acceptance criteria (0.3 gpm at 1000 psig differential pressure) l each time prior to performing this test. Due date: 061598.                                  l
: 2. The IST Coordinator to review the IST Program Plan and QCIS 0200-22 and verify that the procedure adequately implements the ASME Code requirements of the Program Plan and that the implementation of the applicable ASME Code sections are consistent with other Comed BWRs. Due date: 060198.
: 3. As a part of the IST Program assessment and revision effort that is currently ongoing, one objective will be to establish a methodology (e.g., software or            1 checklist) for ensuring adequate documentation that the Program implementation meets the as committed ASME and/or Operations & Maintenance (OMa) part 10 j
requirements, and thus aid in the periodic verification ofIST Program                    i implementation. Due date: 073198.
9                                                                  k 9804080127 980327 PDR    ADOCK 05000254                                                                                /
g                          PDR t.
 
4.
4 USNRC SVP-98-116                              2                  March 27,1998
: 4. IST Coordinator to incorporate this root cause investigation report and the associated LER in the IST Coordinator's position qualification card as required reading. Due date: 063098.
: 5. Instrument Maintenance Department to retest the Unit 2 excess flow check valves at nominal reactor pressure corresponding to 100 percent rated power prior to Unit startup.
: 6. Instrument Maintenance Department to retest the Unit 1 Excess flow check valves at nominal reactor pressure corresponding to 100 percent rated power prior to Unit startup If there are any questions or comments concerning this letter, please refer them to Charles Peterson, Regulatory Affairs Manager at                                        i 309-654-2241, ext. 3609.
Respectfully,
                    /!
David      sager Site Vi      resident Quad Cities Station D'AS/CP/ime cc:      A. B. Beach, Regional Administrator, Region III R. M. Pulsifer, Project Manager, NRR C. G. Miller, Senior Resident Inspector, Quad Cities W. D. Leech, MidAmerican Energy Company D. C. Tubbs, MidAmerican Energy Company M. E. Wagner, Licensing, Comed F. A. Spangenberg, Regulatory Affairs Manager, Dresden INPO Records Center
                                                                                              .
}}
 
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